Tab. 1.2-1: The nuclear power plants currently operating in Switzerland... 3 Tab. 2.6-1: Objectives and principles related to system and staging... 43 Tab. 2.6-2: Objectives and principles related to safety assessment... 44 Tab. 4.2-1: Definition of principal stratigraphic components overlying and underlying
the Opalinus Clay host rock ... 64 Tab. 4.2-2: Properties of regional aquifers and water-conducting formations (minor
aquifers) above and below the host rock formation in the area of interest. ... 77 Tab. 4.2-3: Hydraulic gradients between different formations in the Zürcher Weinland
sedimentary rock sequence ... 79 Tab. 4.2-4: Key results from the hydrodynamic model for the different cases analysed ... 80 Tab. 4.2-5: Average mineralogy of the Opalinus Clay... 85 Tab. 4.2-6: Reference water chemistry of the Opalinus Clay at the Benken site ... 86 Tab. 4.5-1: Model inventories of SF and HLW requiring disposal ... 96 Tab. 4.5-2 Rounded number of disposal canisters of SF and HLW ... 96 Tab. 4.5-3: The total inventories of materials in the ILW, excluding emplacement
containers (cemented waste option) ... 100 Tab. 4.5-4: The rounded number of the various waste drums for disposal of ILW... 100 Tab. 4.5-5: Summary of design variants associated with wastes, engineered barrier
system and repository design and their implications for safety assessment... 110 Tab. 5.2-1: Expected climatic evolution in northern Switzerland for the next one
million years... 113 Tab. 5.2-2: Local geomorphological units representing possible discharge areas of
deep groundwater in northern Switzerland ... 116 Tab. 5.2-3: Relationship between climate and local geomorphological/hydrological
conditions in the surface environment ... 117 Tab. 5.3-1: Calculated redox potentials within bentonite under the assumption of
magnetite/ Fe(II) equilibrium for Fe (II) concentrations equal to those
estimated for Opalinus Clay... 135 Tab. 5.3-2: Compositions of Opalinus Clay reference water (Pearson 2002) and
bentonite porewater... 136 Tab. 5.3-3: Comparison of Kd values of various elements derived from diffusion
experiments with Kunigel V1 bentonite at a dry density of 1800 kg m-3
with those predicted from batch sorption data . ... 147 Tab. 5.5-1: Summary of results of modelling cases examining the transient and
steady-state hydraulic flow impacts of a repository in Opalinus Clay ... 162 Tab. 5.7-1: Key safety-relevant features and phenomena associated with disposal
system evolution ... 172
NAGRA NTB 02-05 XLVIII
Tab. 6.4-1: The proportions of the RTI due to key radionuclides that decay within
different parts of the barrier system for SF, HLW and ILW... 198 Tab. 6.7-1: Possibilities for analysing and presenting results of PSA calculations... 227 Tab. 6.8-1: The significance and treatment in assessment cases of uncertainties and
design / system options associated with specific Super-FEPs ... 237 Tab. 6.8-2: List of scenarios, "what if?" cases, design and system options and
illustration of effects of biosphere uncertainty with associated conceptualisations and parameter variations that define the different assessment cases, structured according to the categories of uncertainty that they address... 250 Tab. 6.8-3: FEPs that are conservatively omitted in defining the assessment cases,
including reserve FEPs... 252 Tab. 7.4-1: Key parameters of the Reference Conceptualisation that are subject to
uncertainties/variability and treatment of key parameters within the
Reference Case and within parameter variations ... 263 Tab. 7.4-2: Summed dose maxima for a single canister, containing various reference
and alternative (hypothetical) canister loadings for SF and HLW... 264 Fig. 7.4-7: Scheme with the conceptual model for gas-induced release of dissolved
radionuclides through the Opalinus Clay and through the access tunnel
system: a) SF, b) ILW ... 279 Tab. 7.9-1: Climate-related parameters used in the modelling of the biosphere
(parameter values for Reference Case biosphere area) ... 311 Tab. 7.10-1: Summary of summed dose maxima for the various scenarios, "what if?"
cases, design and system options and illustration of biosphere uncertainty with associated conceptualisations and parameter variations that define the different assessment cases... 316 Tab. 8.2-1: Understanding of the disposal system and its evolution: evidence and
arguments for safety-relevant characteristics and the selection of parameter values that provide the foundation for the safety case ... 325 Tab. 8.2-2: Summary of maximum annual doses, summed over all radionuclides and
the three waste types SF, HLW and ILW, for the various scenarios, "what if?" cases, design and system options and illustration of biosphere
uncertainty with associated conceptualisations and parameter variations
that define the different assessment cases... 332 Tab. A2.1.1: Inventories of safety-relevant radionuclides in a reference canister
containing 9 BWR UO2 fuel assemblies with a burnup of 48 GWd/tIHM,
after 40 years decay... B-3 Tab. A2.1.2: Inventories of safety-relevant radionuclides in a canister containing 3 PWR
UO2 and 1 MOX fuel assemblies with a burnup of 48 GWd/tIHM, after 40
years decay... B-4 Tab. A2.1.3: Inventories of safety-relevant radionuclides in a canister containing 4 PWR
UO2 fuel assemblies with a burnup of 48 GWd/tIHM, after 40 years decay... B-5
XLIX NAGRA NTB 02-05
Tab. A2.1.4: Average safety-relevant radionuclide content of a single BNFL HLW glass flask, after 40 years decay... B-6 Tab. A2.1.5: Average safety-relevant radionuclide content of a single COGEMA HLW
glass flask, after 40 years decay... B-7 Tab. A2.1.6: Total safety-relevant radionuclide inventory of the ILW-1 disposal tunnels,
after 40 years decay... B-8 Tab. A2.1.7: Total safety-relevant radionuclide inventory of the ILW-2 disposal tunnel,
after 40 years decay... B-9 Tab. A2.2.1: IRF values of key radionuclides for BWR and PWR UO2 fuel and PWR
MOX fuel ... B-10 Tab. A2.2.2: Fractional dissolution rates of spent UO2 and MOX fuel ... B-11 Tab. A2.2.3: Radionuclide release parameters for fuel assembly structural materials ... B-11 Tab. A2.2.4: Other SF near field parameter values... B-12 Tab. A2.3: Reference HLW near field parameter values ... B-13 Tab. A2.4: Solubility limits and associated uncertainties for the SF / HLW near field,
for Reference Case (pH = 7.25, Eh = -194 mV) and for oxidising
conditions ("what if?" case) ... B-14 Tab. A2.5: Solubility limits and associated uncertainties for the cementitious near field
of the waste groups ILW-1 and ILW-2 ... B-15 Tab. A2.6: Sorption values (Kd), effective diffusion coefficients (De) and accessible
porosities (ε) in compacted bentonite: Reference Case (pH = 7.25, Eh = -194 mV) incl. lower (pessimistic) and upper (optimistic) limits,
and "what if?" case for oxidising conditions... B-16 Tab. A2.7: Sorption values (Kd) in cement for the waste groups ILW-1 and ILW-2:
Reference Cases and corresponding lower (pessimistic) and upper
(optimistic) limits... B-17 Tab. A2.8: Sorption values (Kd), effective diffusion coefficients (De┴) and accessible
porosities (ε) in Opalinus Clay... B-18 Tab. A2.9: Transport parameters in Opalinus Clay – Extract of geodataset used in the
modelling of geosphere performance ... B-19 Tab. A2.10: Dose coefficients for inhalation and ingestion... B-20 Tab. A2.11: Biosphere dose conversion factors (BDCFs) ... B-22 Tab. A2.12: Biosphere parameters... B-23 Tab. A2.13: Probability distribution functions (PDFs) for probabilistic calculations ... B-24 Tab. A3.1: Possible comparisons of radioactive waste, or radionuclides released from
the waste, with natural materials... C-1 Tab. A3.2: Dose coefficients (DCs) for ingestion for adult members of the public ... C-2 Tab. A3.3: Activity and toxicity concentrations of natural uranium... C-2 Tab. A3.4: Activity and toxicity concentrations of natural radionuclides in various
uranium ores... C-3
NAGRA NTB 02-05 L
Tab. A3.5: Volumes assumed to calculate the RTI of waste emplacement tunnels
hypothetically filled with natural uranium ores ... C-3 Tab. A3.6: Activity and toxicity concentrations of natural radionuclides in Opalinus
Clay ... C-4 Tab. A3.7: Activity and toxicity concentrations of natural radionuclides in granite and
syenite ... C-4 Tab. A3.8: Activity and toxicity concentrations of natural radionuclides in average soil ... C-5 Tab. A3.9: RTI of spent fuel, vitrified HLW and ILW at selected times... C-5 Tab. A3.10: Possible comparisons of radionuclide fluxes originating from the repository
with natural radionuclide fluxes... C-6 Tab. A3.11: Dose coefficients (DCs) for ingestion of radionuclides dissolved in river or
aquifer water for adult members of the public ... C-6 Tab. A3.12: Concentrations of natural radionuclides and radiotoxicity in the river Rhine
and corresponding radiotoxicity flux ... C-7 Tab. A3.13: Concentrations of natural radionuclides and radiotoxicity in the river Thur
and corresponding radiotoxicity flux ... C-8 Tab. A3.14: Concentrations of natural radionuclides and radiotoxicity of water in
surface aquifers in northern Switzerland and corresponding radiotoxicity
flux ... C-8 Tab. A3.15: Concentrations of natural radionuclides and radiotoxicity of average Swiss
mineral water and the radiotoxicity flux corresponding to an annual
production of 7.7 × 105 m3... C-9 Tab. A3.16: Concentrations of natural radionuclides and radiotoxicity in soil and
radiotoxicity flux due to erosion of soil ... C-10 Tab. A4.1: Roles and interaction of different groups...E-2
LI NAGRA NTB 02-05